reactor code 中文意思是什麼
reactor code
解釋
反應堆計算程序-
The bisonc burnup library is replaced to facilitate the computation of the burnup process with complicated burnup chains. we have made and evaluated the new library ( hendl ) which contains 139 kinds of nuclides with 175 groups for neutron and 42 groups for gamma, 15 kinds of neutron reactions and p0 - p5 expansion. the revised code which we call bus - id is more adaptable to the computation of hybrid reactor for its fuel breeding and the transmutation of the hlw
並且在一維輸運及燃耗計算程序bisonc的基礎上，提出用新的數據庫（ hendl ）代替原有的bisonc數據庫， hendl庫考慮了更加全面的燃耗過程和多種燃料循環方式，通過修正讀入的核截面數據庫中的參數，考慮共振自屏效應，製作並且評估了新的含有139種核素、多種反應截面、 175群中子42群光子、 p _ 0 - p _ 5展開的中子反應數據庫，開發出新的程序bus - 1d ，使得更能適應聚變?裂變混合堆的燃料增殖、高放長壽命核廢料（ hlw ）的嬗變等計算的要求。 -
Test investigation on sgtr of single tube break and three - tube break is carried out on hpitf of ciae to deeply understand the thermal - hydraulic behavior during pressurized - water - reactor ( pwr ) sgtr and to provide an integral data base for code assessment and development. the facility, a full height and 1 / 1000 - scale ( by volume ) of qinshan nuclear power plant, incorporates two identical loops with active pumps and steam generators ( sg ). the initial steady state of the test basically simulated that of the reference plant operation
為了深入了解核電廠蒸汽發生器傳熱管破裂事故發生后的熱工水力現象，以及對壓水堆（ pwr ）核電廠系統分析程序進行分析和評價，在高壓綜合試驗裝置上開展了蒸汽發生器傳熱管破裂試驗研究高壓綜合試驗裝置以秦山核電廠主迴路系統為模擬對象，該裝置為雙環迴路系統，容積比為1 ： 1000 ，高度比為1 ： 1 。 -
In order to promote the development of china ' s nuclear power construction, in the early 1980s, china acquired gratis from the iaea the dot3. 5 code for calculating nuclear reactor safety
為了促進中國核電建設的發展，中國早在80年代初期就從國際原子能機構無償獲得用於計算反應堆安全的計算機軟體程序dot3 . 5 。 -
In the thesis, the relap5 code is made use of simulating and calculating the passive core makeup tank ( cmt ) of the next generation reactor ac - 600 of our country. and the calculative results based on the comparative character of the system are compared with the experimental results in the corresponding experimental devices of ac - 600 makeup water tank in nuclear power institute of china ( npic ). finally the thesis conclusion summarized is that the makeup water passively injected to the reactor coolant system by the core makeup tank depending on the gravity is viable in the middle and small locas
本論文利用relap5程序對我國下一代先進堆ac - 600的一個具有非能動性能的堆芯補水箱分系統進行了模擬計算，根據系統之間的可比性，把計算的結果和與之相對應的中國核動力研究設計院堆芯補水箱補水實驗裝置的實驗結果進行了定性的比較分析，得到了論文的結論：在中、小破口失水事故的工況下，堆芯補水箱依靠重力向反應堆冷卻劑系統實現非能動的補水是可行的。 -
Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 2 ; code for concrete reactor vessels and containments
Asme鍋爐和壓力容器規程.第3節:核設施元部件製造規則.第2分冊.混凝土反應堆容器和外殼規范 -
Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 2 ; code for concrete reactor vessels and containments ; 2005 addenda july 1, 2005
Asme鍋爐和壓力容器規范.第3部分:核設備元件結構原理. 2類.混凝土反應堆容器和安全殼規范.補充件2005
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